1、Designation:E103513Standard Practice forDetermining Neutron Exposures for Nuclear ReactorVessel Support Structures1This standard is issued under the fixed designation E1035;the number immediately following the designation indicates the year oforiginal adoption or,in the case of revision,the year of
2、last revision.A number in parentheses indicates the year of last reapproval.Asuperscript epsilon()indicates an editorial change since the last revision or reapproval.1.Scope1.1 This practice covers procedures for monitoring theneutron radiation exposures experienced by ferritic materials innuclear r
3、eactor vessel support structures located in the vicinityof the active core.This practice includes guidelines for:1.1.1 Selecting appropriate dosimetric sensor sets and theirproper installation in reactor cavities.1.1.2 Making appropriate neutronics calculations to predictneutron radiation exposures.
4、1.2 This practice is applicable to all pressurized waterreactors whose vessel supports will experience a lifetimeneutron fluence(E 1 MeV)that exceeds 1 1017neutrons/cm2or 3.0 104dpa.2(See Terminology E170.)1.3 Exposure of vessel support structures by gamma radia-tion is not included in the scope of
5、this practice,but see thebrief discussion of this issue in 3.2.1.4 This standard does not purport to address all of thesafety concerns,if any,associated with its use.It is theresponsibility of the user of this standard to establish appro-priate safety and health practices and determine the applica-b
6、ility of regulatory limitations prior to use.2.Referenced Documents2.1 ASTM Standards:3E170 Terminology Relating to Radiation Measurements andDosimetryE482 Guide for Application of Neutron Transport Methodsfor Reactor Vessel Surveillance,E706(IID)E693 Practice for Characterizing Neutron Exposures in
7、 Ironand Low Alloy Steels in Terms of Displacements PerAtom(DPA),E 706(ID)E844 Guide for Sensor Set Design and Irradiation forReactor Surveillance,E 706(IIC)E854 Test Method for Application and Analysis of SolidState Track Recorder(SSTR)Monitors for ReactorSurveillance,E706(IIIB)E910 Test Method for
8、 Application and Analysis of HeliumAccumulation Fluence Monitors for Reactor VesselSurveillance,E706(IIIC)E944 Guide for Application of Neutron Spectrum Adjust-ment Methods in Reactor Surveillance,E 706(IIA)E1005 Test Method for Application and Analysis of Radio-metric Monitors for Reactor Vessel Su
9、rveillance,E 706(IIIA)E1018 Guide for Application of ASTM Evaluated CrossSection Data File,Matrix E706(IIB)2.2 ASME Standard:Boiler and Pressure Vessel Code,Section III42.3 Nuclear Regulatory Documents:CodeofFederalRegulations,“FractureToughnessRequirements,”Chapter 10,Part 50,Appendix G5Code of Fed
10、eral Regulations,“Reactor Vessel MaterialsSurveillance Program Requirements,”Chapter 10,Part50,Appendix H5Regulatory Guide 1.99,Rev.1,“Effects of Residual Ele-ments on Predicted Radiation Damage on Reactor VesselMaterials,”U.S.Nuclear Regulatory Commission,April197753.Significance and Use3.1 Predict
11、ion of neutron radiation effects to pressure vesselsteels has long been a part of the design and operation of lightwater reactor power plants.Both the federal regulatory agen-cies(see 2.3)and national standards groups(see 2.1 and 2.2)have promulgated regulations and standards to ensure safeoperation
12、 of these vessels.The support structures for pressur-ized water reactor vessels may also be subject to similar1This practice is under the jurisdiction of ASTM Committee E10 on NuclearTechnology and Applicationsand is the direct responsibility of SubcommitteeE10.05 on Nuclear Radiation Metrology.Curr
13、ent edition approved Jan.1,2013.Published January 2013.Originallyapproved in 1985.Last previous edition approved in 2008 as E103508.DOI:10.1520/E1035-13.2Based on data from Table 5 of Master Matrix E706 and Reference 5.3For referenced ASTM standards,visit the ASTM website,www.astm.org,orcontact ASTM
14、 Customer Service at serviceastm.org.For Annual Book of ASTMStandards volume information,refer to the standards Document Summary page onthe ASTM website.4Available from American Society of Mechanical Engineers,345 E.47th St.,New York,NY 10017.5Available from Superintendent of Documents,U.S.Governmen
15、t PrintingOffice,Washington,DC 20402.Copyright ASTM International,100 Barr Harbor Drive,PO Box C700,West Conshohocken,PA 19428-2959.United States1 neutron radiation effects(1,2,3,4,5).6The objective of thispractice is to provide guidelines for determining the neutronradiation exposures experienced b
16、y individual vessel supports.3.2 It is known that high energy photons can also producedisplacement damage effects that may be similar to thoseproduced by neutrons.These effects are known to be much lessat the belt line of a light water reactor pressure vessel thanthose induced by neutrons.The same has not been proven forall locations within vessel support structures.Therefore,it maybe prudent to apply coupled neutron-photon transport methodsand photon induced displacement cross sections to deter
